JPS63284493A - Frame for supporting reactor pressure vessel - Google Patents
Frame for supporting reactor pressure vesselInfo
- Publication number
- JPS63284493A JPS63284493A JP62117054A JP11705487A JPS63284493A JP S63284493 A JPS63284493 A JP S63284493A JP 62117054 A JP62117054 A JP 62117054A JP 11705487 A JP11705487 A JP 11705487A JP S63284493 A JPS63284493 A JP S63284493A
- Authority
- JP
- Japan
- Prior art keywords
- pressure vessel
- support frame
- iron plates
- reactor pressure
- concrete
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 claims abstract description 30
- 229910052742 iron Inorganic materials 0.000 claims abstract description 15
- 239000004567 concrete Substances 0.000 claims abstract description 11
- 238000010248 power generation Methods 0.000 claims description 5
- 238000009835 boiling Methods 0.000 claims description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 3
- 238000009434 installation Methods 0.000 abstract description 5
- 238000010276 construction Methods 0.000 abstract description 4
- 229910000831 Steel Inorganic materials 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 239000010959 steel Substances 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 230000001629 suppression Effects 0.000 description 2
- 238000004378 air conditioning Methods 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 235000000396 iron Nutrition 0.000 description 1
- 238000009428 plumbing Methods 0.000 description 1
- 239000011150 reinforced concrete Substances 0.000 description 1
- 238000009423 ventilation Methods 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Jib Cranes (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は原子炉圧力容器架台に係り、特に、沸騰水型原
子力発電設備の原子力圧力容器支持架台を貫通する配管
、ケーブルボックス等を内部に収納するのに好適な構造
の支持架台に関するものである。[Detailed Description of the Invention] [Field of Industrial Application] The present invention relates to a nuclear reactor pressure vessel support frame, and in particular, to a nuclear reactor pressure vessel support frame for a boiling water type nuclear power generation facility, in which piping, cable boxes, etc. that pass through the nuclear pressure vessel support frame are installed inside the reactor pressure vessel support frame. The present invention relates to a support frame having a structure suitable for storage.
従来の原子炉圧力容器は、鉄筋コンクリート製あるいは
特公昭６１−６９５５号公報に記載のように鉄板及びコ
ンクリートより構成され、格納容器と圧力容器の相対位
置関係よりその内部に配管あるいはケーブルボックス等
を纏めて収納する空間を構成することについては考慮さ
れていなかった。Conventional reactor pressure vessels are made of reinforced concrete or, as described in Japanese Patent Publication No. 61-6955, made of iron plates and concrete.Due to the relative positioning of the containment vessel and the pressure vessel, piping or cable boxes, etc. are organized inside the vessel. There was no consideration given to configuring the space for storing the items.
また、これまでの沸騰水型原子力発電設備の原子炉圧力
容器支持架台において、−二のような空間を構成する部
材は必要とされていなかった。Further, in the reactor pressure vessel support frames of conventional boiling water nuclear power generation equipment, there was no need for a member constituting a space such as -2.
上記従来技術は、原子炉圧力容器支持架台に配管、ケー
ブルボックス等を纏めて収納することについては配慮が
なされておらず、これらを収納する場合は、支持架台の
建設を容易に、しかも短期間に行うことが困雛であった
。。The above-mentioned conventional technology does not take into account the storage of pipes, cable boxes, etc. all together in the reactor pressure vessel support frame, and when storing these, it is necessary to easily construct the support frame and in a short period of time. It was difficult to do so. .
本発明の目的は、多数の配管、ケーブルボックス等を貫
通させることができ、支持機能を損なうことなく配管、
ケーブルボックス等を収納して放射線、熱等の影響によ
る劣化を防護し、かつ、配管、ケーブルボックス等のサ
ポートを容易にすることができる原子炉圧力容器支持架
台を提供することにある。An object of the present invention is to be able to penetrate a large number of pipes, cable boxes, etc. without impairing the support function.
It is an object of the present invention to provide a nuclear reactor pressure vessel support frame that can accommodate cable boxes and the like to protect them from deterioration due to the effects of radiation, heat, etc., and can facilitate the support of piping, cable boxes, and the like.
上記目的は、多重の円筒型の鉄板と放射状に配置した複
数の鉄板とを一体として複数の開口部を残してコンクリ
ートを注入してなり、上記開口部に配管・ケーブルボッ
クス等を一体化した構成部材を挿通した構成として達成
するようにした。The above purpose is a structure in which multiple cylindrical steel plates and a plurality of radially arranged steel plates are integrated, concrete is poured into the structure leaving a plurality of openings, and piping, cable boxes, etc. are integrated into the openings. The structure is achieved by inserting the member.
多重の円筒型の鉄板と放射状に配列した複数の鉄板とを
一体として複数の開口部を残してコンクリートを注入し
た構成の圧力容器支持架台とし、上記開口部には配管・
ケーブルボックス等を一体とした構造部材を挿通するよ
うにしたので、原子炉圧力容器下部空間に上部空間から
連絡する配管・ケーブルダクト等が多数必要な厚子力発
電設備に有効であり、支持架台の構造体としての機能を
損なうことなく、また、配管等の収納９組み立てのスペ
ースとして必要以上のスペースを確保することを必要と
せず、また、支持架台の組み立て作業と配管等の組み立
て作業を独立して進めることが可能となる。A pressure vessel support frame is constructed by combining multiple cylindrical iron plates and a plurality of radially arranged iron plates, leaving a plurality of openings and pouring concrete into them.
Since a structural member that integrates a cable box etc. is inserted through it, it is effective for Atsuko power generation equipment that requires a large number of piping, cable ducts, etc. that connect from the upper space to the lower space of the reactor pressure vessel. It does not impair its function as a structure, it does not require securing more space than necessary for storing and assembling piping, etc., and it is possible to assemble the support frame and assemble the piping independently. It becomes possible to proceed with
以下、本発明を第１図〜第４図に示した実施例を用いて
詳細に説明する。Hereinafter, the present invention will be explained in detail using the embodiments shown in FIGS. 1 to 4.
第１図は本発明のＪＭ７−炉圧力容器支持架台の一実施
例を示す断面図で、１は原子炉圧力容器支持架台、２は
原子炉格納容器、３は原子炉−法蓮へい、４は支持架台
１に設けた配管・ケーブルボックス等を一体とした構造
部材を挿通する開口部である。なお、１０は圧力抑制室
を示す。FIG. 1 is a sectional view showing an embodiment of the JM7 reactor pressure vessel support frame of the present invention, where 1 is the reactor pressure vessel support frame, 2 is the reactor containment vessel, 3 is the reactor-horen frame, and 4 is the reactor pressure vessel support frame. This is an opening through which a structural member integrated with piping, a cable box, etc. provided on the support frame 1 is inserted. Note that 10 indicates a pressure suppression chamber.
第２図は第１図の支持架台１の横断面図である。FIG. 2 is a cross-sectional view of the support frame 1 of FIG. 1.
支持架台１は、多重の円筒形の鉄板と放射状に配置した
複数の鉄板とを一体とした鉄板５よりなり、複数の開口
部４を残してコンクリートを注入してある。The support frame 1 is made up of an iron plate 5 which is made up of multiple cylindrical iron plates and a plurality of radially arranged iron plates, and concrete is poured into the plate 5 leaving a plurality of openings 4.
第３図は第２図の開口部４内に配管・ケーブルボックス
等を一体化した構造部材６を挿通する吊り込み作業図で
ある。建設時には第３図に示すように、構造部材６をク
レーン１１によって搬入。FIG. 3 is a drawing of a lifting operation in which the structural member 6, which integrates piping, a cable box, etc., is inserted into the opening 4 shown in FIG. 2. During construction, the structural members 6 are brought in by a crane 11, as shown in FIG.
据付けが可能となり、原子炉圧力容器支持架台の建設に
当っては、配管・ケーブルボックス等の据付けに関係な
く、建設が可能となり、支持架台１の一体搬入、据付け
が可能となり、内部コンクリートの打設、養生期間に関
係せず、すべての作業を進めることができる。When constructing the reactor pressure vessel support frame, it is possible to construct the reactor pressure vessel support frame regardless of the installation of piping, cable boxes, etc., and the support frame 1 can be carried in and installed as a whole, and the internal concrete pouring is possible. All work can be carried out regardless of the setting or curing period.
第４図は第１図の原子炉圧力容器支持架台１の開口部４
に構造部材６を挿通した状態の一実施例を示す部分縦断
面図である。第４図において、７は配管、８はケーブル
で、これらが開口部４に挿通できる大きさのサポート９
で支持されて開口部４内に挿通されている。まお、配管
７．ケーブル８等は原子炉圧力容器下部に接続される。Figure 4 shows the opening 4 of the reactor pressure vessel support frame 1 in Figure 1.
FIG. 2 is a partial vertical cross-sectional view showing an example of a state in which a structural member 6 is inserted. In FIG. 4, 7 is a pipe, 8 is a cable, and a support 9 is large enough to allow these to be inserted into the opening 4.
is supported and inserted into the opening 4. Well, plumbing 7. Cable 8 and the like are connected to the lower part of the reactor pressure vessel.
配管７゜ケーブル８は重要度の高いものであり、原子炉
圧力容器からの放射線に対しては、支持架台１の鉄板５
及びコンクリートにより保護され、また、同様にして圧
力容器からの熱に対しても保護されている。また、圧力
抑制室１０に対しても支持架台１の鉄板５及びコンクリ
ートにより保護されており、格納容器２内の換気空調系
により適切な温度。The piping 7° cable 8 is of high importance, and the iron plate 5 of the support frame 1 is protected against radiation from the reactor pressure vessel.
and concrete, and similarly protected against heat from the pressure vessel. In addition, the pressure suppression chamber 10 is also protected by the steel plate 5 of the support frame 1 and concrete, and is kept at an appropriate temperature by the ventilation air conditioning system inside the containment vessel 2.
湿度に保されている。kept moist.
本発明の実施例による支持架台１は、特に原子炉圧力容
器下部空間に上部空間から連絡する配管・ケーブルボッ
クス等が多数必要な原子力発電設備に有効である。The support frame 1 according to the embodiment of the present invention is particularly effective for nuclear power generation equipment that requires a large number of pipes, cable boxes, etc. that connect the lower space of the reactor pressure vessel from the upper space.
以上説明したように、本発明によれば、原子炉圧力容器
支持架台内部に配管・ケーブルボックス等を設置するこ
とが可能であり、また、配管・ケーブルボックス等を一
体化した構造部材を開口部に挿通するだけでよいので、
支持架台の建設を構造部材の据付けと独立して行うこと
が可能であるという効果がある。As explained above, according to the present invention, it is possible to install piping, cable boxes, etc. inside the reactor pressure vessel support frame, and it is also possible to install the structural member that integrates the piping, cable boxes, etc. into the opening. All you have to do is insert it into the
The advantage is that the construction of the support frame can be carried out independently of the installation of the structural elements.
第１図は本発明の原子炉圧力容器支持架台の一実施例を
示す縦断面図、第２図は第１図の支持架台の一実施例を
示す横断面図、第３図は第２図の開口部内に配管・ケー
ブルボックス等を一体化した構造部材を挿通する吊り込
み作業図、第４図は第１図の開口部に構造部材を挿通し
た状態の一実施例を示す部分縦断面図である。
１・・・圧力容器支持架台、２・・・格納容器、４・・
・開口部、５・・・鉄板、６・・・構造部材、７・・・
配管、８・・・ケ率１図
午−−−ＰＦｌｌＯ二台↑
５−一一鉄罹
６− 橋遣揶核。FIG. 1 is a vertical cross-sectional view showing an embodiment of the reactor pressure vessel support frame of the present invention, FIG. 2 is a cross-sectional view showing an example of the support frame of FIG. 1, and FIG. Figure 4 is a partial vertical sectional view showing an example of a state in which a structural member is inserted into the opening shown in Figure 1. It is. 1...Pressure vessel support frame, 2...Containment vessel, 4...
・Opening, 5... Iron plate, 6... Structural member, 7...
Piping, 8...ke ratio 1 figure --- 2 PFllO units ↑ 5-11 irons 6- Hashiyari kokeku.
Claims (1)
鉄板と放射状に配置した複数の鉄板とを一体として複数
の開口部を残してコンクリートを注入してなり、前記開
口部に配管、ケーブルボックス等を一体化した構造部材
を挿通した構成としたことを特徴とする原子炉圧力容器
支持架台。 ２、前記構造部材は前記支持架台完成後に前記開口部に
挿通し、ライナーを介して前記支持架台に固定してある
特許請求の範囲第１項記載の原子炉圧力容器支持架台。[Claims] 1. In a boiling water nuclear power generation facility, multiple cylindrical iron plates and a plurality of radially arranged iron plates are integrated, leaving a plurality of openings and concrete is injected into the openings. 1. A nuclear reactor pressure vessel support frame having a structure in which a structural member integrating piping, a cable box, etc. is inserted through the section. 2. The reactor pressure vessel support frame according to claim 1, wherein the structural member is inserted into the opening after the support frame is completed and is fixed to the support frame via a liner.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62117054A JPS63284493A (en) | 1987-05-15 | 1987-05-15 | Frame for supporting reactor pressure vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62117054A JPS63284493A (en) | 1987-05-15 | 1987-05-15 | Frame for supporting reactor pressure vessel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS63284493A true JPS63284493A (en) | 1988-11-21 |
Family
ID=14702281
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62117054A Pending JPS63284493A (en) | 1987-05-15 | 1987-05-15 | Frame for supporting reactor pressure vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63284493A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2016145756A (en) * | 2015-02-09 | 2016-08-12 | 三菱マテリアル株式会社 | Temperature sensor |
-
1987
- 1987-05-15 JP JP62117054A patent/JPS63284493A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2016145756A (en) * | 2015-02-09 | 2016-08-12 | 三菱マテリアル株式会社 | Temperature sensor |
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